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Title: Performance of Cladding on MOX Fuel with Low 240Pu/239Pu Ratio

The U.S. Department of Energy has decided to dispose of a portion of its surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. As part of fuel qualification, four lead assemblies were manufactured and irradiated to a maximum fuel rod average burnup of 47.3 MWd/kg heavy metal. This was the world s first commercial irradiation of MOX fuel with a 240Pu/239Pu ratio less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. This paper discusses the results of those examinations with emphasis on cladding performance. Exams relevant to the cladding included visual and eddy current exams, profilometry, microscopy, hydrogen analysis, gallium analysis, and mechanical testing. There was no discernible effect of the type of MOX fuel on the performance of the cladding.
Authors:
 [1] ;  [2] ;  [3]
  1. Areva NP
  2. AREVA NP SAS
  3. ORNL
Publication Date:
OSTI Identifier:
1159475
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: Fontevraud 8, Avignon, France, 20140914, 20140918
Research Org:
Oak Ridge National Laboratory (ORNL)
Sponsoring Org:
NNSA USDOE - National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
MOX; Weapons Grade Pu; FMDP; LWR